CN220065196U - Out-of-core nuclear measuring instrument for nuclear reactor - Google Patents
Out-of-core nuclear measuring instrument for nuclear reactor Download PDFInfo
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- CN220065196U CN220065196U CN202321298378.5U CN202321298378U CN220065196U CN 220065196 U CN220065196 U CN 220065196U CN 202321298378 U CN202321298378 U CN 202321298378U CN 220065196 U CN220065196 U CN 220065196U
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Abstract
The utility model provides an off-stack nuclear measuring instrument for a nuclear reactor, which relates to the field of off-stack nuclear measuring instruments and comprises: the protection cabinet comprises different kinds of measuring range equipment; the measuring range device comprises a detector, a conditioning device and a processing device which are connected in sequence; the detector is arranged in the containment of the nuclear reactor, and the conditioning equipment and the processing equipment are arranged in the protection cabinet; the measuring range device measures neutron fluence rate in a sectional way; after the detector reacts with neutrons in the nuclear reactor, an electric pulse signal or a current direct current signal is ionized, the ionized electric pulse signal or current direct current signal is sent to conditioning equipment, a shaped pulse signal or a shaped voltage signal is generated, and the shaped pulse signal or the shaped voltage signal is sent to processing equipment for data operation processing and external communication; the processing equipment is connected with the control cabinet, and the control cabinet is used for summarizing the processed information and sending the summarized information to the whole plant DCS. The utility model realizes localization of the out-of-reactor nuclear measuring instrument of the nuclear power station, so that the system is safer and more reliable.
Description
Technical Field
The utility model relates to the field of off-stack nuclear measuring instruments, in particular to an off-stack nuclear measuring instrument for a nuclear reactor.
Background
An off-stack nuclear instrumentation (reactor nuclear instrumentation, RNI) is a subsystem of a safety level control system for a nuclear reactor, and is configured to monitor the neutron fluence level and the rate of change of the neutron fluence level of the nuclear reactor by a series of neutron detectors mounted outside the pressure vessel, thereby achieving continuous monitoring of the power and changes thereof at all stages of the nuclear reactor from shutdown to power operation.
The RNI of the existing large-scale nuclear power station adopts foreign digital out-of-reactor nuclear instrumentation technology, and in order to realize the localization of the RNI of the large-scale nuclear power station, the RNI which accords with the application of the large-scale nuclear power station is developed by combining the technologies of the traditional small-scale nuclear reactor analog instrument product, the safety digital platform product and the like, and has the characteristics of modularization, digital processing and the like, so that the system is safer and more reliable, and meanwhile, the system has the advantages of automatic test, convenient maintenance, convenient parameter setting and the like.
Disclosure of Invention
The utility model aims to provide an off-stack nuclear measuring instrument for a nuclear reactor, so as to realize localization of the off-stack nuclear measuring instrument of the nuclear reactor and ensure that a system is safer and more reliable.
In order to achieve the above object, the present utility model provides the following solutions:
an off-stack nuclear gauge for a nuclear reactor, comprising: a protection cabinet and a control cabinet;
the protection cabinet comprises different kinds of measuring range equipment; the measuring range device comprises a detector, conditioning equipment and processing equipment which are connected in sequence; the detector is arranged in a containment of the nuclear reactor, and the conditioning equipment and the processing equipment are arranged in the protection cabinet; the measuring range device is used for measuring neutron fluence rate in a segmented way;
after the detector reacts with neutrons in the nuclear reactor, an electric pulse signal or a current direct current signal is ionized, the ionized electric pulse signal or current direct current signal is sent to the conditioning equipment, the conditioning equipment processes the electric pulse signal or current direct current signal to generate a shaped pulse signal or voltage signal, and the shaped pulse signal or voltage signal is sent to the processing equipment for data operation processing and external communication;
the processing equipment is connected with the control cabinet, and the control cabinet is used for summarizing the processed information and sending the summarized information to the whole plant DCS.
Optionally, the detector specifically includes: a source range detector, a mid range detector, and a power range detector;
the source range detector is used for monitoring the neutron fluence rate of the low section; the source range detector is a boron counting tube detector; the boron counting tube detector generates an electric pulse signal and sends the electric pulse signal to source range conditioning equipment corresponding to the source range detector;
the intermediate range detector is used for monitoring neutron fluence rate in the middle section; the intermediate range detector is a compensation ionization chamber detector; the compensation ionization chamber detector generates a direct current signal and sends the direct current signal to middle range conditioning equipment corresponding to the middle range detector;
the power range detector is used for monitoring the neutron fluence rate at high altitude; the power range detector is a non-compensation ionization chamber detector; the uncompensated ionization chamber detector generates six direct current signals and sends the six direct current signals to power range conditioning equipment corresponding to the power range detector.
Optionally, the conditioning device specifically includes: the device comprises an operation unit, a pulse/micro current amplifier, a high-voltage power supply, a compensation power supply and a low-voltage power supply;
the operation unit is respectively connected with the high-voltage power supply and the compensation power supply; the high-voltage power supply and the compensation power supply are also connected with the detector, the pulse/micro-current amplifier and the low-voltage power supply; the operation unit sends a setting signal and a control signal to the high-voltage power supply and the compensation power supply respectively, the high-voltage power supply sends a high-voltage signal to the detector, and the compensation power supply sends a compensation signal to the detector; the detector sends an input signal to the pulse/micro current amplifier, which amplifies and converts the input signal to generate a shaped pulse signal or voltage signal.
Optionally, the processing device specifically includes: the system comprises a controller module, a digital quantity input module, an analog quantity input module, a management module, a communication module, a digital quantity output module, an analog quantity output module and a power supply module;
the controller module is respectively connected with the digital quantity input module, the analog quantity input module, the management module, the communication module and the digital quantity output module; the digital quantity input module is also connected with the pulse/micro-current amplifier; the analog input module is also connected with the high-voltage power supply and the compensation power supply; the digital quantity output module and the analog quantity output module send the output digital quantity and analog quantity to a security level protection logic system, and simultaneously feed back the digital quantity and analog quantity to the operation unit, so that output information can be conveniently tested in a periodic test; the controller module is used for carrying out data operation processing on the shaped pulse signals or voltage signals; the communication module is used for carrying out external communication by adopting optical fibers;
the power module is used for providing power.
Optionally, the control cabinet specifically includes: the system comprises a reactivity instrument interface module, a counting rate sound device, a display screen, an industrial personal computer and a gateway chassis;
the reactivity instrument interface module is used for switching signal interfaces of an off-stack nuclear measurement instrument and a reactivity instrument;
the gateway chassis collects the information processed by the protection cabinet, uploads the collected information to the industrial personal computer, and the industrial personal computer displays the channel information, the equipment state and the alarm information of each measuring range equipment; the channel information comprises channel information of a source range channel, channel information of a middle range channel and channel information of a power range channel;
the counting rate sound device is internally provided with an on-site loudspeaker and is connected with the master control indoor loudspeaker and the safety shell inner loudspeaker; and sending the counting rate information acquired by the source range detector to the counting rate sound device for power amplification, and then driving the local loudspeaker, the master control indoor loudspeaker and the safety shell inner loudspeaker to give out sound to prompt an operator.
Optionally, the industrial personal computer is also connected with a network interface device, and the summarized information is sent to the whole plant DCS.
Optionally, the power range detector is a combination of 6 sections of detectors;
each section of detector is respectively welded with 1 integrated armored cable, and the power range detector is also welded with 1 integrated high-voltage cable; the other end of the integrated armored cable is connected with a connector; the connector of the integrated armored cable is connected with the connector of the coaxial organic cable through a cable connecting plate; the connector of the organic cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with conditioning equipment of a power range;
the 6-section detector shares a shield assembly and a cable junction board.
Optionally, the source range detector welds 1 integrated armored cable, and the other end of the integrated armored cable is connected with a connector; the connector of the integrated armored cable is connected with a coaxial cable through a cable connecting plate; the connector of the organic cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with a source range conditioning device.
Optionally, the intermediate range detector welds 1 integrated armored cable, and the other end of the integrated armored cable is connected with a connector; the connector of the integrated armored cable is connected with the coaxial armored cable through a cable connecting plate; the connector of the armored cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with a source range conditioning device.
Optionally, the method further comprises: a periodic test and maintenance device and an in-situ display device;
the periodic test and maintenance device is connected with each measuring range channel in the protection cabinet and is used for performing periodic test, parameter modification, fault investigation and equipment maintenance on each equipment in the measuring range channel; the measuring range channel comprises a source measuring range channel, a middle measuring range channel and a power measuring range channel; the equipment in the measuring range channel comprises conditioning equipment and processing equipment;
the in-situ display device is connected with the network interface of the processing equipment and is used for modifying the parameters of each measuring range equipment.
According to the specific embodiment provided by the utility model, the utility model discloses the following technical effects: the utility model provides an off-stack nuclear measuring instrument for a nuclear reactor, which is characterized in that a conditioning device in a protection cabinet is used for collecting weak pulse signals or small direct current signals of a detector, the weak pulse signals or the small direct current signals are sent to a processing device in the protection cabinet, the processing device is used for carrying out digital processing and calculation on the weak pulse signals or the small direct current signals, the processed information is sent to an external protection system and a control system, meanwhile, the processed information is sent to the control cabinet of the off-stack nuclear measuring instrument system through optical fiber communication for information summarization, a man-machine interface is realized, and the information is sent to a whole-plant distributed computer control system (Distributed Control System, DCS) to realize localization of the off-stack nuclear measuring instrument of the nuclear reactor, so that the system is safer and more reliable.
Drawings
In order to more clearly illustrate the embodiments of the present utility model or the technical solutions of the prior art, the drawings that are needed in the embodiments will be briefly described below, it being obvious that the drawings in the following description are only some embodiments of the present utility model, and that other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a diagram of an RNI system architecture provided by the present utility model;
FIG. 2 is a block diagram of conditioning apparatus and treatment apparatus provided by the present utility model;
FIG. 3 is a diagram showing the connection between the detector and the protection cabinet according to the present utility model;
FIG. 4 is a graph of the monitoring range of neutron fluence rate in each range channel provided by the utility model.
Detailed Description
The following description of the embodiments of the present utility model will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present utility model, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the utility model without making any inventive effort, are intended to be within the scope of the utility model.
The utility model aims to provide an off-stack nuclear measuring instrument for a nuclear reactor, which can realize the localization of the off-stack nuclear measuring instrument of the nuclear reactor, so that the system is safer and more reliable.
In order that the above-recited objects, features and advantages of the present utility model will become more readily apparent, a more particular description of the utility model will be rendered by reference to the appended drawings and appended detailed description.
The out-of-stack nuclear instrumentation RNI architecture is as follows: the RNI single-unit equipment comprises four sets of protection measuring channel (F-SC 1 level) equipment, 1 control cabinet (hereinafter referred to as a control cabinet) and test and maintenance equipment, wherein the four sets of protection measuring channel equipment are completely identical and are four redundant channels, and a protection logic of 4-out-of-2 is provided for a reactor protection logic system so as to ensure safe and reliable operation of a reactor. Each set of protection measuring channel (F-SC 1 level) equipment comprises 1 nuclear measuring instrument protection monitoring cabinet (hereinafter referred to as a 'protection cabinet') and 1 detector set (comprising a matched coaxial cable and a connector); the control cabinet is used for information collection; the test and maintenance equipment comprises a periodic test and maintenance device and an in-situ display unit.
FIG. 1 is a schematic diagram of an RNI system according to the present utility model, and as shown in FIG. 1, the present utility model provides an off-stack nuclear instrumentation for a nuclear reactor, comprising: a protection cabinet and a control cabinet; the protection cabinet comprises different kinds of measuring range equipment; the measuring range device comprises a detector, conditioning equipment and processing equipment which are connected in sequence; the detector is arranged in a containment of the nuclear reactor, and the conditioning equipment and the processing equipment are arranged in the protection cabinet; the measuring range device is used for measuring neutron fluence rate in a segmented way; after the detector reacts with neutrons in the nuclear reactor, an electric pulse signal or a current direct current signal is ionized, the ionized electric pulse signal or current direct current signal is sent to the conditioning equipment, the conditioning equipment processes the electric pulse signal or current direct current signal to generate a shaped pulse signal or voltage signal, and the shaped pulse signal or voltage signal is sent to the processing equipment for data operation processing and external communication; the processing equipment is connected with the control cabinet, and the control cabinet is used for summarizing the processed information and sending the summarized information to the whole plant DCS.
In practical application, the detector specifically includes: a source range detector, a mid range detector, and a power range detector; the source range detector is used for monitoring the neutron fluence rate of the low section; the source range detector is a boron counting tube detector; the boron counting tube detector generates an electric pulse signal and sends the electric pulse signal to source range conditioning equipment corresponding to the source range detector; the intermediate range detector is used for monitoring neutron fluence rate in the middle section; the intermediate range detector is a compensation ionization chamber detector; the compensation ionization chamber detector generates a direct current signal and sends the direct current signal to middle range conditioning equipment corresponding to the middle range detector; the power range detector is used for monitoring the neutron fluence rate at high altitude; the power range detector is a non-compensation ionization chamber detector; the uncompensated ionization chamber detector generates six direct current signals and sends the six direct current signals to power range conditioning equipment corresponding to the power range detector.
The protection cabinet and the three matched detectors with the detection range capable of being overlapped form a set of protection measurement channel equipment (including a source range channel, a middle range channel and a power range channel).
Each span path includes a processor housing (i.e., processing device), a conditioning housing (i.e., conditioning device), and its detector assembly (including a cable). The conditioning cabinet in the protection cabinet collects weak pulse or small current signals of the neutron detector, and has the main functions of signal amplification and conversion, and the amplified and shaped signals are sent to the processing cabinet for processing; the processor case uses a digital platform module, and the main functions are data operation, logic coincidence and communication. The protection cabinet only has light indication, no other display, various data and parameters are all required to be transmitted to the control cabinet for display by adopting a mode of unidirectional optical fiber transmission through the gateway. The control cabinet comprises a reactivity meter signal interface module, an industrial personal computer, a counting rate sound device (a built-in loudspeaker), a gateway station and other devices, wherein the reactivity meter signal interface module is used for switching signal interfaces of a nuclear instrument system and a reactivity meter; the gateway station receives the information of 4 protection cabinets, uploads the information to an industrial personal computer (provided with man-machine interface software) for displaying and alarming the information of each range channel and the state of equipment, and sends the information to a counting rate sound device through the acquired information of the source range counting rate; the counting rate sound device is used for driving the matched local loudspeaker, the main control indoor loudspeaker and the safe shell internal loudspeaker to give out sound to prompt an operator after power amplification; the gateway station in the control cabinet can receive the measurement data of 4 protection cabinets through the optical fiber, and simultaneously transmit the data to the DCS or the storage equipment through the Ethernet.
Each protection cabinet comprises a source range conditioning case, a source range processor case, a middle range conditioning case, a middle range processor case, a power range conditioning case and a power range processor case.
Due to the variation range of the neutron fluence rate of the nuclear reactor being 10 -1 nv～10 10 nv, the range of variation is big, so divide into three range's equipment and measure, divide into low section, middle section and high section, name respectively as source range (adopting boron count tube detector), middle range (adopting compensation ionization chamber detector), power range (adopting non-compensation ionization chamber detector), and information acquisition, processing, the transportation of corresponding measuring section are accomplished to each range equipment, mutually noninterfere. Three measuring range devices are included in a protection cabinet for protecting the measuring channel, and each measuring range device comprises a processor case and a conditioning case; each chassis is composed of modules or components with different functions, and the modules with the same functions support mutual replacement by adopting a modularized design. The protection cabinet and the matched detector component (including the cable) form a protection measurement channel, and the information of each protection measurement channel is sent to the reactor protection logic system in a hard-wired mode.
In practical application, fig. 2 is a block diagram of conditioning equipment and processing equipment provided by the present utility model, as shown in fig. 2, where the conditioning equipment specifically includes: the device comprises an operation unit, a pulse/micro current amplifier, a high-voltage power supply, a compensation power supply and a low-voltage power supply; the operation unit is respectively connected with the high-voltage power supply and the compensation power supply; the high-voltage power supply and the compensation power supply are also connected with the detector, the pulse/micro-current amplifier and the low-voltage power supply; the operation unit sends a setting signal and a control signal to the high-voltage power supply and the compensation power supply respectively, the high-voltage power supply sends a high-voltage signal to the detector, and the compensation power supply sends a compensation signal to the detector; the detector sends an input signal to the pulse/micro current amplifier, which amplifies and converts the input signal to generate a shaped pulse signal or voltage signal.
The processing equipment specifically comprises: the system comprises a controller module, a digital quantity input module, an analog quantity input module, a management module, a communication module, a digital quantity output module, an analog quantity output module and a power supply module; the controller module is respectively connected with the digital quantity input module, the analog quantity input module, the management module, the communication module and the digital quantity output module; the digital quantity input module is also connected with the pulse/micro-current amplifier; the analog input module is also connected with the high-voltage power supply and the compensation power supply; the digital quantity output module and the analog quantity output module feed back the output digital quantity and analog quantity to the operation unit; the controller module is used for carrying out data operation processing on the shaped pulse signals or voltage signals; the communication module is used for carrying out external communication by adopting optical fibers; the power module is used for providing power.
In practical application, the control cabinet specifically includes: the system comprises a reactivity instrument interface module, a counting rate sound device, a display screen, an industrial personal computer and a gateway chassis; the reactivity instrument interface module is used for switching signal interfaces of an off-stack nuclear measurement instrument and a reactivity instrument; the gateway chassis collects the information processed by the protection cabinet, uploads the collected information to the industrial personal computer, and the industrial personal computer displays the channel information, the equipment state and the alarm information of each measuring range equipment; the channel information comprises channel information of a source range channel, channel information of a middle range channel and channel information of a power range channel; the counting rate sound device is internally provided with an on-site loudspeaker and is connected with the master control indoor loudspeaker and the safety shell inner loudspeaker; and sending the counting rate information acquired by the source range detector to the counting rate sound device for power amplification, and then driving the local loudspeaker, the master control indoor loudspeaker and the safety shell inner loudspeaker to give out sound to prompt an operator.
In practical application, the industrial personal computer is also connected with a network interface device, and the summarized information is sent to the whole plant DCS.
Control cabinet: the control cabinet comprises an industrial personal computer, a display, a counting rate sound device (a built-in loudspeaker), a gateway station and other equipment. The function is that the gateway station in the cabinet communicates with each measuring range processor case device in the protection cabinet of four nuclear measuring channels, and the communication mode adopts a mode of point-to-point unidirectional communication by optical fibers, so that the operation or failure of the control cabinet can be ensured not to influence the work of each functional module in the protection cabinet. All the information of the four nuclear measurement channels is collected, then the gateway station sends the information to an industrial personal computer host in a control cabinet, the host sends one path of information to a display to display the information, the other path of information is sent to a whole plant DCS through a network interface device connected with the industrial personal computer, meanwhile, the industrial personal computer discriminates a source range pulse counting rate signal representing a power state, sends the pulse counting rate to a counting rate sound device (a built-in loudspeaker) through a switching value channel to send loudspeaker dripping sound with the same frequency as the counting rate, and prompts a reactor operator to the power state of the reactor.
In practical application, fig. 3 is a diagram showing a connection between the detector and the protection cabinet, as shown in fig. 3, where the power range detector is a combination of 6 sections of detectors; each section of detector is respectively welded with 1 integrated armored cable, and the power range detector is also welded with 1 integrated high-voltage cable; the other end of the integrated armored cable is connected with a connector; the connector of the integrated armored cable is connected with the connector of the coaxial organic cable through a cable connecting plate; the connector of the organic cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with conditioning equipment of a power range; the 6-section detector shares a shield assembly and a cable junction board.
In practical application, 1 integrated armored cable (NMIT-400) is welded to each 6-section detector to output signals, meanwhile, 1 integrated high-voltage cable is used for providing working voltage for each 6-section detector, 7 integrated armored cables are connected with a low-noise coaxial cable (THJHP/D) connector through a cable connecting plate and used for transmitting analog signals sensitive to interference, 7 low-noise coaxial cables are connected with a penetrating piece of a containment vessel through the connector at the other end of the penetrating piece and then connected with an organic cable connector outside the containment vessel, and the other end of the connected organic cable is connected with power range conditioning cabinet equipment in a protection cabinet.
In practical application, the source range detector is welded with 1 integrated armored cable, and the other end of the integrated armored cable is connected with a connector; the connector of the integrated armored cable is connected with a coaxial cable through a cable connecting plate; the connector of the organic cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with a source range conditioning device.
In practical application, the intermediate range detector is welded with 1 integrated armored cable, and the other end of the integrated armored cable is connected with a connector; the connector of the integrated armored cable is connected with the coaxial armored cable through a cable connecting plate; the connector of the armored cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with a source range conditioning device.
In practice, the source range detector and the mid range detector share a shielding assembly and a cable connection plate.
The source range detector comprises an integrated armored cable (NMIT-400), the integrated armored cable is provided with a connector on a cable adapter plate and is connected with a high electromagnetic interference resistant coaxial cable (PK 2XS 024), and after a penetrating piece of the safety shell is connected with the high electromagnetic interference resistant coaxial cable (PK 2XS 711) outside the safety shell, signals are sent to a conditioning cabinet device for protecting the source range of the cabinet, each section of coaxial cable is provided with a matched cable connector for switching, and the source range detector and the middle range detector share a set of shielding assembly and a cable connection plate.
The intermediate range detector also comprises an integrated armored cable (NMIT-400), the integrated armored cable is provided with a connector and is connected with a low-noise coaxial cable (THJHP/D) on the cable adapter plate, the other end of the integrated armored cable is connected with the low-noise coaxial cable (THJHP/D) outside the safety shell through a penetrating piece of the safety shell, and finally the integrated armored cable is connected with intermediate range conditioning cabinet equipment of the protection cabinet, and signals of the detector are sent to the conditioning cabinet for processing. The intermediate range detector and the source range detector share a set of shielding assembly and a cable connection board.
The coaxial cable with the shielding layer transmits the interference-sensitive analog signals to each measuring range conditioning unit in the protection cabinet directly, so that the reliability of signal transmission is ensured.
The connection of such detectors to the cabinet has been verified in various identification tests of product prototypes.
In practical application, the method further comprises the following steps: a periodic test and maintenance device and an in-situ display device;
the periodic test and maintenance device is connected with each range channel in the protection cabinet when the high voltage and the threshold value are periodically tested or modified, and is used for carrying out periodic test, parameter modification, fault investigation and equipment maintenance on each equipment in the range channel; the measuring range channel comprises a source measuring range channel, a middle measuring range channel and a power measuring range channel; the devices within the span passageway include conditioning devices and processing devices.
Periodic test and maintenance device: in the periodic test and maintenance device, an internal signal generator simulates a detector to output a signal, and the signal is sent to a protection cabinet conditioning device for amplification and shaping during test, and then the information processed by the protection cabinet processing device is acquired by a data acquisition PLC system, and the automatic test and functional performance judgment of the whole process are completed by automatic running software and set judgment basis, so as to obtain a test report. The information can be displayed through a display for periodic test, and the whole process supervision can be performed. The working state of the RNI system can be regularly judged and guaranteed through regular tests, and the normal operation of the system is guaranteed.
The in-situ display device is connected with the network interface of the processing equipment and is used for modifying the parameters of each measuring range equipment.
In-situ display unit: the system is movable computer equipment, engineer station software of a digital platform is installed, and parameters of each measuring range can be modified through a network interface of processor box equipment of each measuring range of the protection cabinet.
FIG. 4 is a graph showing the monitoring range of neutron fluence rate in each measuring range channel provided by the utility model, and as shown in FIG. 4, the relation between neutron fluence rate corresponding to three measuring range devices in the protection measuring channel and power value corresponding to a reactor is described, and the sensitivity of a source measuring range detector is more than or equal to 8 cps/n.cm -2 ·s -1 The method comprises the steps of carrying out a first treatment on the surface of the The sensitivity of the intermediate range detector is more than or equal to 8 x 10 -14 A/n·cm -2 ·s -1 The method comprises the steps of carrying out a first treatment on the surface of the The sensitivity (each section) of the power range detector is more than or equal to 2.3 x 10 -14 A/n·cm -2 ·s -1 。
Three measuring range equipment in the protection cabinet are set up the principle: since the meter measurement range spans 11 orders of magnitude, namely: from start-up to 200% power level (corresponding to a reactor neutron fluence rate of 1 x 10) -1 nv～1×10 10 nv), thus using three of Source Range (SR), intermediate Range (IR) and Power Range (PR)The segment measurements are made by different means. The neutron fluence rate of 6 orders of magnitude at the low section of the source range monitoring; neutron fluence rates of 7 to 8 orders of magnitude in the middle range monitoring section; the power range is used for measuring the neutron fluence rate of the high section, namely the neutron fluence rate of 3 orders of magnitude in the high section, when the reactor is in normal operation.
The neutron fluence rate measuring ranges of the three measuring ranges are overlapped by at least 2 orders of magnitude so as to ensure reliable transition between the measuring ranges. The three measuring ranges are respectively composed of different neutron detectors, conditioning equipment and processing equipment, wherein the neutron detectors are placed in a containment of a reactor, and the conditioning equipment and the processing equipment are placed in a protection cabinet.
The working principle of the protection cabinet is as follows: the detector can ionize weak electric pulse signals or small current direct current signals after reacting with neutrons, the weak electric pulse signals or small current direct current signals are transmitted to the conditioning equipment cabinet equipment of the protection cabinet through the anti-interference double-shielding long cable to perform amplification, screening, shaping and other works, and the shaped pulse or voltage signals are sent to the processor cabinet equipment corresponding to the conditioning equipment cabinet of each measuring range to complete the functions of data operation, logic coincidence, external communication and the like of the signals.
The detector comprises: the detector is a sensor for collecting the neutron fluence rate information of the reactor, and three detectors are commonly used in the RNI: boron counting tube, compensating ionization chamber, non-compensating ionization chamber. The boron counting tube generates a micro-current pulse signal and is mainly connected with source range conditioning equipment in the protection cabinet; the compensating ionization chamber and the non-compensating ionization chamber can generate small direct current signals, and are respectively connected with conditioning equipment with intermediate range and power range in the protection cabinet.
The detector of the RNI mainly aims at converting neutron fluence rate into pulse or current signals and sending the pulse or current signals to the conditioning cabinet.
In the present specification, each embodiment is described in a progressive manner, and each embodiment is mainly described in a different point from other embodiments, and identical and similar parts between the embodiments are all enough to refer to each other.
The principles and embodiments of the present utility model have been described herein with reference to specific examples, the description of which is intended only to assist in understanding the methods of the present utility model and the core ideas thereof; also, it is within the scope of the present utility model to be modified by those of ordinary skill in the art in light of the present teachings. In view of the foregoing, this description should not be construed as limiting the utility model.
Claims (10)
1. An off-stack nuclear gauge for a nuclear reactor, comprising: a protection cabinet and a control cabinet;
the protection cabinet comprises different kinds of measuring range equipment; the measuring range device comprises a detector, conditioning equipment and processing equipment which are connected in sequence; the detector is arranged in a containment of the nuclear reactor, and the conditioning equipment and the processing equipment are arranged in the protection cabinet; the measuring range device is used for measuring neutron fluence rate in a segmented way;
after the detector reacts with neutrons in the nuclear reactor, an electric pulse signal or a current direct current signal is ionized, the ionized electric pulse signal or current direct current signal is sent to the conditioning equipment, the conditioning equipment processes the electric pulse signal or current direct current signal to generate a shaped pulse signal or voltage signal, and the shaped pulse signal or voltage signal is sent to the processing equipment for data operation processing and external communication;
the processing equipment is connected with the control cabinet, and the control cabinet is used for summarizing the processed information and sending the summarized information to the whole plant DCS.
2. The out-of-stack nuclear gauge for a nuclear reactor of claim 1, wherein the detector comprises, in particular: a source range detector, a mid range detector, and a power range detector;
the source range detector is used for monitoring the neutron fluence rate of the low section; the source range detector is a boron counting tube detector; the boron counting tube detector generates an electric pulse signal and sends the electric pulse signal to source range conditioning equipment corresponding to the source range detector;
the intermediate range detector is used for monitoring neutron fluence rate in the middle section; the intermediate range detector is a compensation ionization chamber detector; the compensation ionization chamber detector generates a direct current signal and sends the direct current signal to middle range conditioning equipment corresponding to the middle range detector;
the power range detector is used for monitoring the neutron fluence rate at high altitude; the power range detector is a non-compensation ionization chamber detector; the uncompensated ionization chamber detector generates six direct current signals and sends the six direct current signals to power range conditioning equipment corresponding to the power range detector.
3. The out-of-stack nuclear gauge for a nuclear reactor according to claim 1, characterized in that said conditioning device comprises in particular: the device comprises an operation unit, a pulse/micro current amplifier, a high-voltage power supply, a compensation power supply and a low-voltage power supply;
the operation unit is respectively connected with the high-voltage power supply and the compensation power supply; the high-voltage power supply and the compensation power supply are also connected with the detector, the pulse/micro-current amplifier and the low-voltage power supply; the operation unit sends a setting signal and a control signal to the high-voltage power supply and the compensation power supply respectively, the high-voltage power supply sends a high-voltage signal to the detector, and the compensation power supply sends a compensation signal to the detector; the detector sends an input signal to the pulse/micro current amplifier, which amplifies and converts the input signal to generate a shaped pulse signal or voltage signal.
4. The out-of-stack nuclear gauge for a nuclear reactor according to claim 3, characterized in that said processing means comprise in particular: the system comprises a controller module, a digital quantity input module, an analog quantity input module, a management module, a communication module, a digital quantity output module, an analog quantity output module and a power supply module;
the controller module is respectively connected with the digital quantity input module, the analog quantity input module, the management module, the communication module and the digital quantity output module; the digital quantity input module is also connected with the pulse/micro-current amplifier; the analog input module is also connected with the high-voltage power supply and the compensation power supply; the digital quantity output module and the analog quantity output module send the output digital quantity and analog quantity to a security level protection logic system, and simultaneously feed back the digital quantity and analog quantity to the operation unit, so that output information can be conveniently tested in a periodic test; the controller module is used for carrying out data operation processing on the shaped pulse signals or voltage signals; the communication module is used for carrying out external communication by adopting optical fibers;
the power module is used for providing power.
5. The out-of-stack nuclear gauge for a nuclear reactor of claim 2, wherein the control cabinet comprises in particular: the system comprises a reactivity instrument interface module, a counting rate sound device, a display screen, an industrial personal computer and a gateway chassis;
the reactivity instrument interface module is used for switching signal interfaces of an off-stack nuclear measurement instrument and a reactivity instrument;
the gateway chassis collects the information processed by the protection cabinet, uploads the collected information to the industrial personal computer, and the industrial personal computer displays the channel information, the equipment state and the alarm information of each measuring range equipment; the channel information comprises channel information of a source range channel, channel information of a middle range channel and channel information of a power range channel;
the counting rate sound device is internally provided with an on-site loudspeaker and is connected with the master control indoor loudspeaker and the safety shell inner loudspeaker; and sending the counting rate information acquired by the source range detector to the counting rate sound device for power amplification, and then driving the local loudspeaker, the master control indoor loudspeaker and the safety shell inner loudspeaker to give out sound to prompt an operator.
6. The off-stack nuclear gauge for a nuclear reactor of claim 5, wherein the industrial personal computer is further connected to a network interface device to send the aggregated information to the whole plant DCS.
7. The off-stack nuclear gauge for a nuclear reactor of claim 2, wherein the power range detector is a combination of 6-segment detectors;
each section of detector is respectively welded with 1 integrated armored cable, and the power range detector is also welded with 1 integrated high-voltage cable; the other end of the integrated armored cable is connected with a connector; the connector of the integrated armored cable is connected with the connector of the coaxial organic cable through a cable connecting plate; the connector of the organic cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with conditioning equipment of a power range;
the 6-section detector shares a shield assembly and a cable junction board.
8. The out-of-pile nuclear gauge for a nuclear reactor of claim 2, wherein the source range detector welds 1 integral armoured cable with a connector connected to the other end of the integral armoured cable; the connector of the integrated armored cable is connected with a coaxial cable through a cable connecting plate; the connector of the organic cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with a source range conditioning device.
9. The out-of-pile nuclear gauge for a nuclear reactor of claim 2, wherein the mid-span detector welds 1 integral armored cable with a connector connected to the other end of the integral armored cable; the connector of the integrated armored cable is connected with the coaxial armored cable through a cable connecting plate; the connector of the armored cable is connected with the containment penetration piece; the connector at the other end of the containment penetration is connected with the connector of the cable outside the containment; the connector of the external cable is connected with a source range conditioning device.
10. The off-stack nuclear gauge for a nuclear reactor of claim 1, further comprising: a periodic test and maintenance device and an in-situ display device;
the periodic test and maintenance device is connected with each measuring range channel in the protection cabinet and is used for performing periodic test, parameter modification, fault investigation and equipment maintenance on each equipment in the measuring range channel; the measuring range channel comprises a source measuring range channel, a middle measuring range channel and a power measuring range channel; the equipment in the measuring range channel comprises conditioning equipment and processing equipment;
the in-situ display device is connected with the network interface of the processing equipment and is used for modifying the parameters of each measuring range equipment.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202321298378.5U CN220065196U (en) | 2023-05-26 | 2023-05-26 | Out-of-core nuclear measuring instrument for nuclear reactor |
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| CN202321298378.5U CN220065196U (en) | 2023-05-26 | 2023-05-26 | Out-of-core nuclear measuring instrument for nuclear reactor |
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